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JERSEY CENTRAL POWER 6 LIGilT COMPANY

OYSTER CREEK NUCLEAR GENERAT[NG STATION

Provisional OperatingLicense No. DPR-16

Technical SpecificationChange Request No. 74Docket No. 50-219

Applicant submits, by this Technical Specification Change RequestNo. 74 to the Oyster Creek Nuclear Generating Station Technical Specifications,revising section 3.4. A.10 and section 3.S. A.2 concerning draining of the torus.

JERSEY CE RAL PO 'ER LIGliT COMPANY.

BY: ,-

~Vice Pre en

STATE OF NEW JERSEYCOUNTY OF MORRIS

Sworn and subscribed to before me on this 24th day of Sept. 1979,,

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Pl!Y'Lll3 A. I'A3!Snor..m , c u: cr t,tw Jf GEY

MyCen;, :n Egi :s Ass. 16.1984

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UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSION

IN THE MATTER OF )) DOCKET NO. 50-219

JERSEY CENTRAL POWEP S LIGHT COMPANY )

CERTIFICATE OF SERVICE

This is to certify that a copy of Technical Specification Change

Request No. 74 for the Oyster Creek Nuclear Generating Station Technical

Specifications, filed with the U. S. b'uclear Regulatory Commission on

has this 24th day of September,1979, been served on theSeptember 24,

Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United

States mail addressed as follows:

The Honorable Marylou SmithMayor of Lacey TownshipP. O. Box 475Forked River, New Jersey 08731

JERSEY CENTRAL P0FER S LIGHT COMPANY

!BY:Vice Pr ide

DATED: September 24, 1979

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Jersey Central Power & Light Company,

3 (J - - --

,{f f y-)~

McJison Avenue at Punch Bowl Road'' -

. Mornstown, New Jersey 07960(201)455-8200

September 24, 1979

The Honorable Marylou SmithMayor of Lacey TownshipP. O. Box 475Forked iver, New Jersey 08731

Dear Mayor Smith:

Enclosed herewith is one copy of Technical Specification ChangeRequest No. 74 for the Oyster Creek Nuclear Generating Station TechnicalSpecifications.

These documents were filed with the U. S. Nuclear RegulatoryCommission on September 24, 1979.

Very truly yours,

hag,Ivan R. Finfro ,,JVice Presiden

cb

Enclosure

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Jersey Central Power & Lght Company is a Member of the General Public Utilit:es System

JERSEY CENTRAL POWER & LIGHT CmPANY

OYSTER CREEK NUCLEAR GENERATING STATION

(DOCKET NO. 50-219)

PROVISIONAL OPERATING LICENSE NO. DPR-16

Applicant hereby requests the Commission to change Appendix A to the abovecaptioned license as follows:

1. Sections to be changed:

Section 3.4.A.10 and section 3.5.A.2.

2. Extent of changes:

Revise the above sections to allow draining the torus withouthaving to meet the requirement of removing the reactor vessel head ,fuel pool gate and separator-dryer gate and raising the water levelabove elevation 117 feet.

3 Changes requested:

Replace revised pages 3.4-la, 3.4-1b, and 3.5-1a.

4. Discussion:

This Technical Specification change will revise Section 3.4 and3.5 to allow draining of the suppression pool without having to removethe vessel head and fuel, separator-dryer pool gates.

To ensure an adequate water supply to the vessel, while thesuppression pool is drained , certain prerequsites to draining thetorus have to be met. These prerequisites include:

a. An operable flow path capable of taking suction from thecondensate storage tank and transferring water to the reactor vessel.

b. The fire protection system is op;rable.

c. At least one core spray pump, and system componentsnecessary to deliver rated core spray flow to the reactor vessel mustremain operable to the extent that the pump and any necessary valvescan be started or operated frcm the control roan or from local controlstations, and the torus is mechanically intact.

d. The condensate storage tank level is maintained greaterthan thirty (30) feet (360,000 gallons).

In the unlikely event that a drain path is established which

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would have the potential to drain the reactor vessel, the condensatestorage tank would provide the necessary makeup volune needed to keepthe core covered. Several flow paths may be used to transfer the watersuch as filling the hotwells from the condensate storage tank andusing the condensate system to transfer this water to the reactorvessel or using the core spray system to transfer the water to thereactor vessel from the condensate storage tank. By requiring that thecondensate storage tank level be maintained greater than thirty (30)feet will ensure that there is sufficient water inventory available ,should the le~ak go unchecked, to fill the lower portion of thedrywell, empty into the torus and fill the suction header of the corespray system (330,000 gallons) . The core spray system can then belined up to recirculate the water to the reactor vessel.

The fire protection system will be used as a backup source ofmakeup water should it be required. There is sufficient volume in thefire pond to provide the makeup water necessary to place the corespray system in operation to recirculate water to the reactor vessel.

To further minimize the possibility of draining the vessel, arequirement that no work shall be performed on the vessel which couldresult in lowering the reactor water level to less than 4'8" above thetop of the active fuel will be in effect while the torus is drainedunless the reactor vessel head, fuel pool gate, and separator-dryerpool gates are removed and the water level is above elevation ',17feet. This requirement will assure that there is a ready source ofmakeup water available while work is being performed which could havethe potential of draining the vessel.

With alternate sources of water available and a requirement thatno work be performed which could have the potential of draining thereactor vessel, this proposed change request will not increase theprobability of an accident or risk to the health and safety of thepublic.

as

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3.4-1a

a. At least one core spray pump, and systemcomponents necessary to deliver rated core sprayto the reactor vessel, must remain operable to theextent that the pump and any necessary valves canbe started or operated from the control room orfrom local control stations.

b. The fire protection system is operable, and

c. These systems are denonstrated to be operableon a weekly basis.

8. If necessary to accomplish maintenance or modifications to the corespray systens, their power supplies or water supplies, reduced systenavailability is permitted when the reactor is in the refuel mode withthe reactor coolant system maintained at less than 212 F or in thestartup mode for the purposes of low power physics testing. Reducedcore spray system availability is defined as follows:

a. At least one core spray pump in each loop, andsystem components necessary to deliver rated corespray to the reactor vessel, must remain operableto the extent that the pump and any necessaryvalves in each loop can be startec or operatedfrom the control room or from local controlstations.

b. The fire protection system is operable and,

c. Each core spray pump and all components in3.4. A.8a are demonstrated to be operable every 72hours.

9. If Specifications 3.4.A.7 and 3.4.A.8 cannot be met, therequirements of Specification 3.4. A.6 will be met and work will beinitiated to meet minimum operability requirements of 3.4. A.7 and

3.4.A.8.

10. The core spray system is not required to be operable when thefollowing conditions are met:

a. The reactor mode switch is locked in the" refuel" or " shutdown" position.

b.(1) There is an operable flow path capable oftaking suction from the condensate storage tankand transferring water to the reactor vessel, and

(2) The fire protection system is operable.

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3.4-1b

c. The reactor coolant system is maintained atless than 212 F and vented.

d. At least one core spray pump, and systemcomponents necessary to deliver rated core sprayflow to the reactor vessel, must remain operableto the extent that the pump and any necessaryvalves can be started or operated from the controlrcom or from local control stations, and the torusis mechanically intact.

e.(1) No work shall be performed on the reactor orits connected systems which could result inlowering the reactor water level to less than 4'8"above the top of the active fuel and thecondensate storage tank level is greater thanthirty (30) feet (360,000 g allons) .

OR

(2) The reactor vessel head, fuel pool gate, andseparator-dryer pool gates are removed and thewater level is above elevation 117 feet.

NOTE: When filling the reactor cavityfrom the condensate storage tank anddraining the reactor cavity to thecondesate storage tank, the 30 footlimit does not apply provided there issufficient amount of water to ccmpletethe flooding operation.

B. Autcmatic Depressurization Systen

1. Five electromatic relief valves of the automatic depressurizationsystem shall be operable when the reactor is pressurized above 110psig, except as specified in 3.4.B.2.

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3.5-1a

c. The reactor coolant system is maintained atless than 212 F and vented.

d. At least one core spray pump, and systemcomponents necessary to deliver rated core sprayflow to the reactor vessel, must remain operableto the extent that the pump and any necessaryvalves can be started or operated from the controlroom or from local control stations, and the torusis mechanically intact.

e.(1) No work shall be performed on the reactor orits connected systems which could result inlowaring the reactor water level to less than 4'8"above the top of the active fuel and thecondensate storage tank level is greater thanthirty (30) feet (360,000 gallons) .

OR

(2) The reactor vessel head, fuel pool gate, andseparator-dryer pool gates are removed and thewater level is above elevation 117 feet.

NOTE: When filling the reactor cavityfrom the condensate storage tank anddraining the reactor cavity to thecondensate storage tank, the 30 footlimit does not apply provided there issufficient amount of water to canpletethe flooding operation.

3. Primary containment integrity shall be maintained at all times whenthe reactor is critical or when the reactor water temperature is above212 F and fuel is in the reactor vessel except while perfonning lowpower physics tests at atmospheric pressure during or after refuelingat g>wer levels not to exceed 5 Et.

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